Information and flow diagrams are presented from a presentation on tritium research and development activities at the Mound Laboratory. Topics include metal-hydrogen systems, gas dynamics and cryogenic separations, materials research, and helium diffusion and tritium effluent control.

This paper describes the Mound plutonium study. The objectives of the project were to evaluate the inventory of plutonium 238 in the environment at Mound, determine the source, and alleviate potential health hazards. Analysis of soils, water, vegetation, fishes, and runoff were performed.

This report details the status of the testers which provide the testing support of timers, actuators, detonators, firing sets, transducers, isolators, and pyrospacers during the time period of October through December 1978.

The main efforts of the past year have been directed towards investigation of the behavior of the radioactive aerosols in actual in mining operations. Activities can be categorized as follows: Preparation of equipment for taking data in uranium mines; development of background of personnel to carry out intended experiments; research data from United Nuclear Homestake Partners Section 25 mine in the Ambrosia Lake area near Grants, New Mexico; updating of computer programs for data analysis in order to extract more information; and the development of a thermal precipitator for partical size analysis in the submicron range.

This report covers all nondestructive development effort on the Roll Control Program for the period June 1, 1976 through December 15, 1976. Information previously reported will be re-presented here and appropriately updated. The samples consist of solid propellant and composites of propellant and inhibitor that are currently being examined in the accelerated aging and shelf life prediction studies of materials involved in the B-77 Roll Control Program.

Results of preliminary study are presented which was performed under subtask 2.7 of the NTS Terminal Waste Storage Program Plan for 1978. Subtask 2.7 examines the feasibility of locating a nuclear waste repository in a granitic stock or pluton in southern Nevada near the Nevada Test Site (NTS). It is assumed for the purposes of this study that such a repository cannot be located at NTS. This assumption may or may not be correct. This preliminary report does not identify a particular site as being a suitable location for a repository. Nor does it absolutely eliminate a particular site from further consideration. It does, however, answer the basic question of probable suitability of some of the sites and present a systematic method for site evaluation. Since the findings of this initial study have been favorable, it will be followed by more exhaustive and detailed studies of the original 30 sites and perhaps others. In future studies some of the evaluation criteria used in the preliminary study may be modified or eliminated, and new criteria may be introduced.

High purity nitrate esters of the pentaerythritols can be successfully synthesized from correspondingly high purity reagents. The latter are not commercially available, but may be purified through molecular distillation and/or fractional crystallization from xylene. The isolated products are ultimately saponified to reagents of high purity. The nitration of high purity pentaerythritols using 97-100% nitric acid proceeds smoothly resulting in yields of the corresponding nitrate esters which are nearly quantitative. Thin layer chromatography (TLC) indicates numerous satellite impurities present in all the pentaerythritol-tetranitrate (PETN) homologs with the exception of ultrapure PETN itself. Separation and isolation of these contaminants, from a high impurity concentrate, was achieved by liquid chromatography. IR spectra of these components suggests these compounds are the various homologs and pentaerythryl ethers with a mixture of hydroxyl and nitrate functional groups.

This document presents details of the status of irradiations performed by Fuel and Target Irradiation Technology for BNW as of January 31, 1970.

Distribution coefficients have been determined for {sup 137}Cs, {sup 85}Sr, {sup 144}Ce, {sup 99}Tc, {sup 152}Eu, {sup 238}Pu, {sup 244}Cm, and {sup 243}Am between argillite from the Eleana Formation on the Nevada Test Site (NTS) and several aqueous phases. Radionuclide concentrations in the range of 1 to 0.001 {mu}Ci/ml were used with contact times of 14, 28, and 56 days. Reaction mechanism, concentration effects, exchange capacity, equilibration times, and particle size effects were addressed in a more comprehensive study of the interaction of argillite with Cs in deionized water. The experimental parameters used in the distribution coefficient measurements were based in part on this work. The aqueous phases included a simulated groundwater with composition based on the analysis of a NTS groundwater, the same simulant and deionized water which were pre-equilibrated with powdered argillite, and a groundwater simulant with approximately the same qualitative composition of the NTS simulant, but with a higher ionic strength. A system to provide continuous pH control by CO{sub 2} addition during equilibration of the argillite-solution mixtures was designed and assembled. Initial experiments were done with Cs and Eu and the effects of pH on their distribution coefficients are discussed.

This document contains the details the activities of Douglas United Nuclear at the Hanford Reservation during the month of January 1970.

If we are to believe our predictions of the thermomechanical behavior of the material surrounding a nuclear waste repository in granite, we must test the computational methods used in making the predictions. If thermal loadings appropriate to a real repository are used, thermally induced displacements and strains are quite small, and available geotechnical instrumentation is only marginally able to measure these effects to the accuracy desired to make thorough tests of the predictions. We outline a three-step program to address these issues. (1) Conduct experiments in which the thermal loading is large compared to that induced by a real repository. This will permit us to make accurate measurements with available instrumentation. (2) Simultaneously, develop improved instrumentation that will enable us to make accurate measurements of motions induced by thermal loadings appropriate to a real repository. (3) Finally, conduct a second set of experiments, with the improved instrumentation and thermal loading similar to that of a real repository in granite. If we can predict the effects of this thermal loading to a few percent over distances of tens of meters for time periods of a few years, and demonstrate that these predictions are correct, we can have reasonable confidence that, using …

This report describes and presents the results of an analysis of the performance of the infrared acquisition system for a Self-Initiated Antiaircraft Missile (SIAM). A description of the optical system is included, and models of target radiant intensity, atmospheric transmission, and background radiance are given. Acquisition probabilities are expressed in terms of the system signal-to-noise ratio. System performance against aircraft and helicopter targets is analyzed, and background discrimination techniques are discussed. 17 refs., 22 figs., 6 tabs.

This paper is a reflection on the current understanding of the unprotected transient overpower (TOP) accident, in order to place it in perspective with regard to FFTF core energetics. The experimental data base is addressed, wtih particular emphasis on the E and H-series data, and its relevance to axial failure location and hydraulic fuel sweepout is considered. It is shown that the only way in which TOP could lead to a sizeable energy release is if either total plugging takes place or a plug at the radial center of the subassemblies propagates to the hex can walls prior to neutronics shutdown. (DLC)

This is the eighth in a series of quarterly progress reports on studies performed for the Alternate Fuel Cycle Technologies/Thorium Fuel Cycle Technologies/International Spent Fuel Receipt and Storage (AFCT/TFCT/ISFS) Program, formerly the LWR Fuel Recycle Program. This program is designed to provide information needed by industry to close the back end of the power reactor fuel cycle. During the past quarter, studies were conducted in the following tasks: Survey of Current Technology of Fuel Handling Techniques; Investigation of Air Cleaning Processes for Removing Tributyl Phosphate (TBP) from Off-Gas Streams; Study of Iodine Chemistry in Process Solutions; Electropolishing to Decontaminate Metallic Waste from Alternate and Thorium Converter Fuel Cycles; and U.S. Scale Transport, Dispersion and Removal Mode Comparison Safety Criticality Experiments. (11 figs., 7 tables)

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This paper presents data for 20 potential liquid-dominated hydrothermal resources postulated for development in the 1977-1990 timeframe and analyzes the needs for their development. The paper comprises a summary of the needs identified followed by 20 individual data files, one for each site. The paper is directed towards deriving implications from site-specific analyses of postulated development. The areas covered by the analysis include land leasing and major site-specific development milestones, technology R&D, and economics. The individual reservoir-specific data and development analysis files contain data on the physical, geological and geothermal characteristics of each site, the estimated development schedule (with major milestones), and projected economics. [DJE-2005]

Due to the continuing high air sample results over the past six months, a thorough review of conditions and procedures was felt necessary for 325-B facility. A complete survey of the facility was made, looking for possible or definite problems. A discussion about procedures and conditions was held with all Radiation Monitoring personnel involved with the facility. The following items we felt needed attention to improve the working environment for the personnel in the facility. 1. Recommend glovebox be decontaminated and gloves changed to reduce dose rates. 2. Repair fume hood for proper airflow. 3. Move slurp jug inside fume hood and provide lead shielding. 4. Change storage of samples outside of cells to reduce dose rates. 5. Recommend contaminated waste from cells be bagged when removed through transfer tray. 6. Recommend fume hoods be installed at cell transfer trays. During a recent house cleaning, personnel in 325-B took action to correct items number 1 through 5, which leaves item number 6 to be considered. The need for fume hoods is based on high air sample results. These fume hoods would be very helpful in the unpackaging of contaminated samples. The removal of samples from the cell requires good air …

Project reports on ecological research authored by scientists from several PNL research departments and grouped primarily by the energy technologies to which they relate are compiled.

A precision dc voltage reference has been constructed to serve as a driver for a regulated direct current source used in the callbration of ammeters, resistors, and shunts. Variable output voltages are generated by dividing the output of a 10-V supply (CODI Semiconductor Inc. Model PVS10CA) to a nominal 0.16 and 1.6 V, selected by range switching. These voltages are applied to the input of a 320-k{Ohm}, six-decade, Kelvin-Varley divider, the output of which is used to drive the regulated direct current source. Provision has been made for precision adjustment of the input voltages to the Kelvin-Varley divider. The resolution of the output voltage is 0.625 ppm of full scale, with an estimated uncertainty of {+-}50 ppm of the setting or {+-}10 {micro}V, whichever is greater. The voltage reference is easy to use, and it has improved measurement accuracy.

Information pertinent to solid waste burial sites under the control of Battelle-Northwest is provided. In particular, data are tabulated for given sites providing the acreage of the given burial sites, dates of activation and deactivation or continued active status, buried waste volume, waste type according to what radiations are emitted, grams of beta and gamma emitters and plutonium buried, how the plutonium is contained, and term of storage (i.e., long term). A map of the Hanford area is provided giving the locations of some of the burial grounds. Finally, a page of descriptive information is given for each site giving the status, reference drawing number, location, description, and contents.

The current national program comprises the following major activities: (1) preliminary design, systems studies, and cost estimates for a reference 'pilot-plant' driver [Beam energy = 1 MJ; Beam power on target = 100 TW; specific energy deposition {ge} 20 MJ/gm]; (2) consequent upon this reference design, definition of an intermediate Heavy Ion Demonstration Experiment (HIDE) to test the accelerator technology and to begin to probe the scaling behavior of the heavy-ion target behavior, current thinking suggests that the beam energy should be about 100 kJ, or roughly one-tenth that of the reference design, in present DOE plans, HIDE is assumed to be operating in FY1985 or FY1986. (3) Design of targets optimized for heavy-ion driver; relaxation of the high beam-power requirements would allow accelerator designs to produce lower kinetic energy for the ion and permit a longer final pulse duration, thus easing a difficult demand on present-day accelerator behavior; (4) development of a clear understanding of the design implications of the beam space-charge limits, both longitudinal and transverse, several of the accelerator system design parameters, e.g apertures, number of final beams, size of final focusing magnets, are sensitive to assumptions about the six-dimensional phase-space density and volume of the beam. …

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Primary recoil distributions and specific damage energies have been computed for high energy deuteron-breakup neutrons in Cu, Nb, and Au. The calculations are based on theoretical neutron cross sections, and consider in particular a d-Be spectrum broadly peaked at 15 MeV with some neutrons above 30 MeV. The theoretical results are similar to corresponding calculations for monoenergetic 15-MeV neutrons and are in good agreement with range measurements of (n,2n) recoils generated by high energy d-Be neutrons in Nb and Au. The calculations are also consistent with recent d-Be neutron sputtering experiments in Nb and Au and demonstrate the usefulness of deuteron-breakup neutron sources for simulating fusion neutron effects. (auth)

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